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He replacement technologies; Development of HLNB counterTanigawa, Masafumi; Mukai, Yasunobu; Nakamura, Hironobu; Kurita, Tsutomu; Henzlova, D.*; Menlove, H. O.*
Dai-37-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2017/02
no abstracts in English
Kureta, Masatoshi; Koizumi, Mitsuo; Ozu, Akira; Furutaka, Kazuyoshi; Tsuchiya, Takahiro*; Seya, Michio; Harada, Hideo; Abousahl, S.*; Heyse, J.*; Kopecky, S.*; et al.
Proceedings of 37th ESARDA Annual Meeting (Internet), p.111 - 120, 2015/08
The JAEA has just started the new program "Development of active neutron NDA techniques" collaborating with EC-JRC. The final purpose of this program is to establish the measurement techniques for the high radioactive special nuclear material such as MA-Pu fuel for transmutation of minor actinide and for nuclear security applications. In this program, JAEA will conduct the R&D on active neutron non-destructive measurement techniques, DDA, NRTA, PGA/NRCA and DGS.
Mochiji, Toshiro;
JNC TN1450 2000-001, 122 Pages, 2000/03
JNC-TN1450-2000-001.pdf:6.39MB
no abstracts in English
Ogawa, Hironobu; Mukaiyama, Takehiko
Dai-11-Kai Kaku Busshitsu Kanri Gakkai Nenji Taikai Rombunshu, p.83 - 90, 1990/06
no abstracts in English
Tomikawa, Hirofumi; Watahiki, Masaru; Kuno, Yusuke
no journal, ,
Japan is the only non-nuclear-weapon country with nuclear fuel cycle facilities including uranium enrichment and reprocessing facilities. The evolution of technologies has been instrumental in improving facility and safeguards efficiency. Older facilities with small material throughput operated almost manually. In contrast, more modern facilities with large material throughput were designed for improved throughput and accountancy and introduced state-of-art safeguards technologies. Japan has the experience of a series of new types of nuclear facilities which are pilot scale through commercial size. This paper presents the efforts and evolutions of the safeguards technology development introduced to the bulk handling facilities including uranium enrichment, reprocessing and MOX fuel fabrication facilities in Japan, through international cooperation. The evolution of technologies has benefited both the State/Operator and the IAEA.
Nomi, Takayoshi; Nagatani, Taketeru; Shiromo, Hideo; Asano, Takashi
no journal, ,
This report describes applicability evaluation results of the passive neutron technique (PN) for characterization study of candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station. The PN consists of Differential Die-away Self-Interrogation (DDSI) and neutron coincidence counting. The DDSI evaluates the neutron multiplication and absorption effect and corrected coincidence count rate determines Cm-244 effective mass. Nuclear material is quantified by using isotopic composition from code calculation or 
ray measurement. The simulation results indicate that the PN is applicable to B-10 contained fuel debris. The results also indicate that the major uncertainty factor is the variation of water content. To minimize it, classification of rough water fill ratio in a canister such as wet storage or dry storage will be required.
Nomi, Takayoshi; Nagatani, Taketeru; Kosuge, Yoshihiro*; Shiromo, Hideo; Asano, Takashi
no journal, ,
no abstracts in English
Nomi, Takayoshi; Nagatani, Taketeru; Kosuge, Yoshihiro*; Shiromo, Hideo; Asano, Takashi
no journal, ,
Okazaki, Hiro; Sumi, Mika; Kayano, Masashi; Matsuyama, Kazutomi; Suzuki, Toru; Kuhn, E.*
no journal, ,
For the effective and efficient implementation of international Safeguards, it is essential that the Operator's measurement system is maintained at a level of high quality and improved, as necessary. Besides the internal quality control, it is important to have elements of Quality Assurance (QA) in place, such as external intercomparison. However, there were no intercomparison programs with Plutonium samples available in Japan because of very few users and difficulties in the shipment of such samples from foreign laboratories. To cope with these difficult situations, intercomparison by using actual safeguards samples containing Plutonium and Uranium was started. Inspection samples are selected and prepared for shipment to the Safeguards laboratories together with other samples. Safeguards laboratories receive and analyze them as inspection samples as well as intercomparison without additional cost for analysis operation or sample transportation. The practicality and effective use of this DA intercomparison, which is operated since more than 20 years, will be explained.